ML20085H190
| ML20085H190 | |
| Person / Time | |
|---|---|
| Site: | Saxton File:GPU Nuclear icon.png |
| Issue date: | 11/30/1966 |
| From: | SAXTON NUCLEAR EXPERIMENTAL CORP. |
| To: | |
| Shared Package | |
| ML20083L048 | List:
|
| References | |
| FOIA-91-17 NUDOCS 9110280160 | |
| Download: ML20085H190 (8) | |
Text
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7 u a . s. . s. ~,sa .mug.wa.u a . na 0Mrationn hemrt for_ !!ovenber loM:
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- 1. OplERAL The scheduled plant outage which was begun on October 14th was continued .
until Novanber 19th.
The major work effort during this shutdown was devoted toward advancing the construction status of the supercritical technology test loop. The piping work was done by Pittsburgh Pipe and & tuipment Company of Pittsburgh, Pa. and the electrical work was done by Electrical Contractor Associates, Inc. of Altoona, Pa.
The work was supervised by engineering personnel of the Vestinghouse Atomic Power Division.
On llovember 7th the supercritical loop unfueled pressure tube that had been installed in reactor cora position N-4 for piping tit-up was removed. The dummy assembly was reinstalled in core position N-4 on Novenber 14th. The period November 15th thru November 10th was utilized in restoring the reactor vessel head to nomal operating conditions and in performing minor maintenance on the nain coolant and auxiliary systems. Filling and venting of the main coolant system and pressure testing it to 500 psig was completed on November 19th. Heat-up to 2500 F using the main coolant punp and pressuriner heaters was completed on November 20th.
2, }tEACTOR OPERATIONS The reactor was made critical at 5:20 PM on November 20th and was used to
. heat the main coolant system from 250 0 F to nornal operating tanperature.
At 10:30 PM the reactor scramed fron zero power dur.4ng the transfer of the main coolant pump from the nornal 440 volt, 60 cycle power supply to the variable frequency motor generator set. The scran circuit was set up when the nomal supply breaker was opened before the under-frequency, 27 5 cycles, protection relay on the motor-generator set had cleared.
The reactor was made critical at 7:26 AH on Novanber 21st for scheduled low power physics tests, but was shutdown again because a pressurizer safety valve, V-373, was sinnering. The safety valve was resented and reactor operation was resumed at 2:20 M!. Iow power physics tests were completed at 11:50 M1 and the reactor was manually shutdown so that entry could be made to the containment vessel for maintenance '
work on a component cooling system pump.
At 5:40 M4 on November 22nd the reactor was made critical and start-up of the secondary system was conmer.ced. Reactor power range channel "A" did not respond to the power increase. The reactor power level was reduced to below 103 of full power and held until repairs were nade to the power supply for power range channel "A". Secondary system start-up was resumed at 10:15 PM. The #2 generator was synchronized on the line
- at 10
- 31 FM and the reactor was then loaded to 23 5 Mit.
Reactor plant operation at a power level of 23 5 Mit was continued through the remainder of.the month.
l 9110290160 010424 PDR FOIA DEMOK91-17 PDR E __ _ _ ._ _ _ _ _ . _ . _ . - - _ _ . _ _ - - - _ . . -.-- _ _ _ , __ . _ . -
SNLC Operations Hoport for t
i ovember 1%6 . , , . #2 3 EXPZ1111 ENTAL PIWHtAH A cuccessful hydrostatic test was performed on the supercritical technolm test loop on Nova ber 17th.
On Novenber 21st the average burn-up on the reactor core was 5713 MIDNTF.
An all rods out, xenon free, just critical main coolant boron concentration was detemined for an average nain coolant temperature of 530 0F. The boron concentration for these conditions was 1260 pps.
A complete xenon buildin was followed for the start-up initiated on Noveaver 22nd. Tne equilibrium xenon for 23.2 Mit was detemined to be 2.26% ok/k in reactivity.
On Novenber 27th the radiation monitoring system circuits were tested.
5 f.AINTE"ANCE The principal items of nochanical maintenance during the month included lapping the seats of the remote operated valves HIC-24V and HIC-27V in the charging synta'a; lapping the seating ourfaces in regenerative heat exchanger relief valve V-53; removing, cleaning and reinstalling the tube bundle in the storage well system heat exchanger; inspecting the neat and plug in the purification system letdown valve UIC-21V; installing a new stator in thc sample pump; replacing the filter cartridges in the purification syntem pre-post filter; installing a new mechanical seal on co:.ponent cooling pump No. 2; replacing a section of underground pipe in the condensate retum line for the monitor tank steam heating system; replacing the plugs in several valves un E!DF gav decay tanks No. 2 & No. 3; repacking the steam shut-off valves to the recircu1Ating oductor for the EiDF lig.id storage tanks; repairing the
' drain on a sink in the chenistry laboratory; replacing the eductor in the EIDF ever.porator feed line; cleaning the UlDF evaporator with a caustic solution; replacing a shear j pin on the rotary crane in the containment vessel; repacking plungers No. 2 and No. 3 on charging pump No. 2; flushing the air handler in the control rod drive mechanism
[
room; removing the unfueled supercritical loop pressure tube from reactor core position N-4 and reinstalling the dummy assembly in that position; restoring the reactor vessel l
i head to operating conditions; pressure testing the TiWDF evaporator tubes and tube sheets; cleaning the BlDF evaporator rupture dice line; and setting the relieving pressure on the regenerative heat exchanger relief valve, V-53.
The major items of instrument and electrical n.aintenance included inspecting the nuclear instrumentation detector cables for radiation damage; replacing the cable seals on the detectors for nuclear instrumentation power range channels A and C; l
installing new filter paper in containment vessel particulate monitor RIC-1 and in site particulate monitor RIC-9; calibrating the EIDF evaporator hotwell activity monitor, RIC-7; installing a new 0-M tube in the containment vessel particulate monitor, RIC 1; repairind the leak-off system alam; replacing a defective diaphragm
U:M 4eratient Report for llover.ber 19M . . . . . fl in the mercoid "Ki-lo" preocure alam evitch for the decentanitation room liquid storage tanks replacing a position indicating cwitch vn !!IG29V in the shutdoun cooling cystemt replacing the solenoid operated air control valves for runote operated valves HIC-23V and HIC-27V in the purification system; installing a new BF3 neutron detector in the neutron detecting channel that is used for fuel handling in the containt.cnt vecsels replacing an "0" ring in the flowmeter for the nixed bed denineralizer in the water treating s;' stem; c)eaning the unloading valve on the instranent air compressor; repairing the pressure gauge tap on llo.1 cation resin tank in the water treating systen; checking the specific gravity of the station batteries; installing new vanes in the vacuum pump for a portable alpha particulate monit ort replacing the air regulator in the control air syt> ten for the pressurizer spray valvel repairing the horn on the water treatment alam panel; calibrating the ga:ra, energy opectrometer in the count room; stroking the steam regulating va3ve, V-1010, to the deaerator and cleaning the controller on the valve; checkinr, the vo: Lages on the cathodic protection systen; and adjusting the rod drop alarm relay for control rod six.
- 6. CHDlISTRY The main coolant systen was in cold shutdown condition during the first nineteen days of the month. Hydrazine was added on 1;ovember 17th in preparatier for rystea heat-up. The main conlant systen was nuccessfully leak tested at opercting temperature on liovenber 21ct. Hydrogen was added on llovenber 22nd in preparation for power o;mrativn.
A suutar;' of the analyses made on main coolant samples taken during the month is contained in the following table:
Main Coolant Sycten Minimum Maximum pH at 25 0 5.35 6.31 Conductivity, unhos 4.11 10.35 Ibron, pga 742 1362
- 40.0 Gross Beta-Gamma Il5 Min. degassed) ue/cc 0.352
- 4.21 Tritium,ue/cc 3.27x10-2 1.23x10-1
- Cold Shutdown Condition A storage well fater sample that was analyzed for crud shoved 141 ppb.
The average activity of the steam generator for the r.onth was less than 1 x 10-8 ue/ce. Except for a chort period after start-up on llovember 22nd, the steam generator chlorides were maintained at less than 0.275 ppm.
Nil.C Operatione Report for
- Hovember 10% . . . . . i/4 i 7 RADI ATIOll /C UASTE FI,SPOSA', t Radiation surveyinc coneiuted of routine plant surveys, C.V. during i,nutdown and materials shipnents. The following naxinum readings were takent Incation [tadiation Readin; C!d. Build!n2 Vaste Drun (baling machine) 70 mrem /hr beth-gama Charging Pump (contact with chamber) 70 mren/hr beta-gama Sample Room (door of sample panel) 7 mrem /hr beta-gmna 14 mrem /hr beta-ganna Chenical Inb Hot Sink (1" from drain) ,
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}r m F Evaporator (under botton) 30 mrcm/hr beta-gamma Evaporator (contact outside upper level) 22 mrem /hr beta-gama '
Drun Storage Area (at HRA fence) 4.5 mrem /hr beta-gama C.V.
Prinary Compartment (general upper level) 100 mrem /hr beta-gama 300 mrem /hr beta-ga:ma Pri:voy Compartment (contact H.C. pump volute)
Primary Conpartnent (S.G. botton) 250 mrem /hr beta-sama Primry Compartment (pressuriser bottom) 260 mrem /hr beta-ganma Prinary Conpartment (general lower level) 00 mrem /hr beta-gama >
Prinary Conpartnent (regen. H.X.) 220mram/hrbeta-gxm .
Primary Compartnent (non-regen. H X.) 180 mrem /hrbeta-gamma Aur.iliary Equip. Compartment (S.C.H.I.) 100 mrem /hr beta-gamma Auxiliary Equip. Compartment (D.T. top) 80 mram/hr beta-gamma Auxiliary Fquip. Compartment (D.T. bottan) 320 mrem /hr beta-ganma Auxiliary Equip. Compartment (general lower level) 40 mrm/hr beta-gama Reactor Dech (water level at grating) 4 mram/hr beta-gama Reactor Deck (instranent ports) 700 mrem /hr beta-cama ReactorDeck(uaintlevel) 50 mrem /hr beta-ccama ReactorDoch(storagewellrailing) 4 mrem /hr beta-gama Fd s eellaneous Four (4) shipments of clothing used during STP fabrication work were made to laundry Contractor (maximum for all shipments - contact) 1.0 mr/hr beta-gama One (1) shipment of tools and equipnent to Waltz Mill (contact) 1.0 mr/hr beta-gama G
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L!C0 Operationo Report for lhve%rr 1%6 . , ,, . .J Conttc.ination surveying conciated of routine plant site surveys, surveys of v.aterials shipped, tools, equipment and C.V. during thutdown. The clean arene were within the " Clean Area" linito. The controlled areas were generally within the
" Clean Area" linits. The controlled area was cicaned frequently to keep and/or to return it to the " Clean Area" linits. The exclusion arcac were cicaned periodically to minilaice the mount of oneurable contanination. The following cantamination levels were observed Inchtion Conta.ination Readine Ch.A Duildinr. ;
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Charging Pump Chanber 339210 d/m/encar beta-garna l Charging Punp Chanber < 10 d/m/ smear alpha Charging Roon Floor 6400 d/m/cmear beta-ganna Sanple Roan Sink 3406 d/m/ smear beta-gamma Sanple Room Sink d 10 d/m/ smear alpha Sanple Rocci Floor 600 d/m/ smear beta-gama Chemical lab Hot Sink ~405326 d/m/smearbeta-ganma Chemical lab Hot Sink 4.10 d/m/snear alpha WDF Shipping Room Floor 279 d/m/nmear beta-camma C.V.
Operating Deck 4000 d/m/ smear beta-gamma Prinary Compartnent (grating) 55352d/m/smearbeta-ga*xaa Liquid and gaseous effluents from the SIEC site for the month of Novenber 1966 were as fo11ovat (Curie) (Curie) (Curie)
Effluent Activity Activity Activity Type This Month Year to Date last Twelve Months Liquid 0.000961 0.0105778 0.013563 Air, Xe 0.198733 99.972473 100.557993 Air, I-131 c.000232 0.110140 0.116105 Afr, H.F.P. 0.001987 0.999725 1.005580 Tiitium 0.096128 15.713211 21.620658
'D ere was no waste drummed for storage or shipped from the site during the month.
Ra t ation exposure for all SIEC p, v. .. as measured by film badges for the month of .:ctober 1966 were a maximum of .. nrem with an average of 57.4 mre.
SICC Operations Report for
!!ovember 1966 . . . . . #6 Radiation exposure for all visiting personnti as measured by fiba badges for the month of October 1966 were a maximum of 375 nrem with an average of 36.6* mrm.
The average radiation exposure for all personnel as ceasured by filn badges for the month of October 1966 was 47.8 nrem.
- Includes all cont.: actor personnel for supercritical constraction 1
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SAXTON NUCLEAR EXPERIMEtTTAL CORPORATION OPERATING STATISTICS MONT}{ November YEAR 1966 NUCLTAR UNIT HONT'l Hf8 ,TO DATE NO. 3 33 488
' TIMES CRITICAL HRS. 212.4 5497 97 18380.10 -
HOURS CRITICAL NO. 2 22 284 TIMES SCRAMMED (MANUAL)
NO. 1 2 31 ,
- TIMESQCRAMMED(INADVERTANT)
MWH 4525 12 120325 25 329570.08 THERMAL POWER GENERATION WD$fu 369 37 9021 79 9883 51 AVERADE BJRNUP CONTROL ROD POSITIONS AT WD OF HONTH AT MUILIIRIUM PWER OF 23.44 mt MAIN 0001 ANT BORON 751 PPM RODS 007 - INCHES 40 No, 2 29.15 NO 3 40 NO. 1 40 Wo. 5 40 Wo. 6 40 NO. 4 ,
EIECTRICAL WIT g gfg gg tgTg OROSS GENERATION WH 8$8.00 211% 1.00 55523.00 HWH 154.47 2270.24 10472.53 STATIObSERVICE
$ 18.00 10.69 18.86 STATION SERVICE 5 18.96 17 65 16.85 AVO. PIANT EFFICHNCY - WH(e)/WH(t)
AVO. GENERATION NJNNINO (194.75 HRS) W 4405.65 4003.19 3324.99 PIANT IIMD FACTOR - 58.88 30.38
$ 26.73 (AVO. GEN.FORNONTH/kAX.IIMD) fUXILIARY STEAM SUPPLY - NUCLEAR STEAM SUPPLIED Bf REACTOR HRS. 197 5 5336.28 15035.25 WDF EV APORATOR OPERATION HRS. 0 1523.58 35a4.83
- RD! ARKS: The inadvertant scram on Novanber 20, 1966 occurred when the main coolant pump was transferred from its nonnal 440V supply to the variable freguency motor generator set.
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